[en] Twelve Exxon Nuclear fuel assemblies presently in the Kahl Boiling Water Reactor core are sealed with FAID ultrasonic seals. The sealing system in this demonstration experiment is designed to meet safeguards, reactor safety, and fuel handling requirements. Results of these ongoing experiments are presented. 3 references, 1 figure

[en] The ARC/SPAR sealing system, based on an ultra-sonic signature and designed for sealing CANDU-type spent fuel, has been undergoing field evaluation at Gentilly-2 600 MW Reactor for the last ten months. The test was designed to evaluate the hardware and software of the system, the effort required for the application and verification of the containment and seals, the interference with operator, the procedures and the false- and missed alarm rates. Routine use conditions were emphasized throughout the test. In the course of the trial the entire content of the spent fuel in the pond was sealed. Preliminary results indicate that the system is acceptable. Hardware, software and procedures except for the transducer worked well. Transducer failure occurred too frequently at an unacceptable rate. The problem was identified and will hopefully be overcome. Level of intrusion with operations could be considered acceptable. Inspectors carrying out seal application and verification were adequately trained and performed satisfactorily. Auto- and crosscorrelations are reported. Recommendations are made for the improvement of equipment and procedures. The test will continue until the end of this year

[en] This is a part of the result of the research jointly done, based on the research agreement RA NO. 3215/CF, by IAEA and the University of Tokyo with Mr. Yosuke Ichino, an observer from Nuclear Safeguards Bureau, Science and Technological Agency of Japanese Government (JNSB) from the Period, August 2, 1982 - August 1, 1983. In light of the safeguard importance of the high strategic value of nuclear material at sensitive facilities, containment and surveillance (C/S) is a measure to achieve timely detection of diversion of nuclear material. As such, at YAYOI facility, a prototype core seal surveillance meter (CSSM) was developed. This paper describes design, fabrication, installment, functional test results, and the start of tentative application. All the functions were tested and confirmed satisfactory except the material of the control box (now a steel box instead of anodized aluminum box which is necessary for tamper preclusion). (author)